TXX-4600, Final Deficiency Rept SDAR-193 Re Potential Loss of Control Capability of Feedwater Regulating Valve.Initially Reported on 850827.Condition Not Reportable Under 10CFR50.55(e): Difference between revisions

From kanterella
Jump to navigation Jump to search
VisualWikitext
StriderTol Bot insert
 
StriderTol Bot change
 
Line 19: Line 19:
* 400 NOR Til OIJ% E NTHEET, L.H. N R
* 400 NOR Til OIJ% E NTHEET, L.H. N R
* ID A R.R.AM. TEW AN 75 20 8
* ID A R.R.AM. TEW AN 75 20 8
  .*nTJ A.*Sf,735                                     October 16, 1985 Mr. R. P. Denise, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76012                                                                             l)CT ? I lg85
. nTJ A.*Sf,735 October 16, 1985 Mr. R. P. Denise, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76012 l)CT ? I lg85


==SUBJECT:==
==SUBJECT:==
COMANCHE PEAK STEAM ELECTRIC STATION l                       DOCKET NOS. 50-445 AND 50-446 l                       AUXILIARY FEEDWATER SYSTEM l                       QA FILE:         CP-85-32, SDAR-193
COMANCHE PEAK STEAM ELECTRIC STATION l
DOCKET NOS. 50-445 AND 50-446 l
AUXILIARY FEEDWATER SYSTEM l
QA FILE:
CP-85-32, SDAR-193
{
{


==Dear Mr. Denise:==
==Dear Mr. Denise:==
 
On August 27, 1985, we verbally notified a ur Mr. T. Westerman of a deficiency regarding the potential loss of control capability of the feedwater regulating valve due to the valve's power supply being located in the cable spread room. We have submitted an interim report logged TXX-4567, dated September 24, 1985.
On August 27, 1985, we verbally notified a ur Mr. T. Westerman of a
l We have completed our investigation and concluded that the matter is not l
,          deficiency regarding the potential loss of control capability of the feedwater regulating valve due to the valve's power supply being located in the cable spread room. We have submitted an interim report logged TXX-4567, dated September 24, 1985.
reportable under 10 CFR 50.55(e). Records supporting this determination are available for your inspector's review at the CPSES site.
l           We have completed our investigation and concluded that the matter is not l           reportable under 10 CFR 50.55(e). Records supporting this determination are available for your inspector's review at the CPSES site.
Very truly yours, il
Very truly yours, il         .
? o tE[
                                                                                                              ? o tE[
W. G. Counsil
W. G. Counsil By:            /     t'' '
/
T. S. Marshall Licensing Supervisor JCH/grr c-   NRC Region IV (0 + 1 copy)
t''
By:
T. S. Marshall Licensing Supervisor JCH/grr c-NRC Region IV (0 + 1 copy)
Director, inspection & Enforcement (15 copies)
Director, inspection & Enforcement (15 copies)
U. S. Nuclear Regulatory Commission Washington, D.C. 20555 8510280500 851016 5
U. S. Nuclear Regulatory Commission Washington, D.C.
gefh)                   {DR ADOCK 050
20555 8510280500 851016 gefh)
                                                                                                                              ]
{DR
a nuusuns or rex A., uruturn:s us>:enuc < our a xv                                   -
]
Q
ADOCK 050 5
                                                                                              -.}}
Q a nuusuns or rex A., uruturn:s us>:enuc < our a xv
-.}}

Latest revision as of 08:24, 12 December 2024

Final Deficiency Rept SDAR-193 Re Potential Loss of Control Capability of Feedwater Regulating Valve.Initially Reported on 850827.Condition Not Reportable Under 10CFR50.55(e)
ML20133N304
Person / Time
Site: Comanche Peak  
Issue date: 10/16/1985
From: Counsil W, John Marshall
TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To: Denise R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
SDAR-193, TXX-4600, NUDOCS 8510280500
Download: ML20133N304 (1)
v • d • e


Text

Log e TXX-4600 TEXAS UTILITIES GENERATING COMPANY File 7 10110 h3(Y H A Y TOW EN

  • 400 NOR Til OIJ% E NTHEET, L.H. N R
  • ID A R.R.AM. TEW AN 75 20 8

. nTJ A.*Sf,735 October 16, 1985 Mr. R. P. Denise, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76012 l)CT ? I lg85

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION l

DOCKET NOS. 50-445 AND 50-446 l

AUXILIARY FEEDWATER SYSTEM l

QA FILE:

CP-85-32, SDAR-193

{

Dear Mr. Denise:

On August 27, 1985, we verbally notified a ur Mr. T. Westerman of a deficiency regarding the potential loss of control capability of the feedwater regulating valve due to the valve's power supply being located in the cable spread room. We have submitted an interim report logged TXX-4567, dated September 24, 1985.

l We have completed our investigation and concluded that the matter is not l

reportable under 10 CFR 50.55(e). Records supporting this determination are available for your inspector's review at the CPSES site.

Very truly yours, il

? o tE[

W. G. Counsil

/

t

By:

T. S. Marshall Licensing Supervisor JCH/grr c-NRC Region IV (0 + 1 copy)

Director, inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C.

20555 8510280500 851016 gefh)

{DR

]

ADOCK 050 5

Q a nuusuns or rex A., uruturn:s us>:enuc < our a xv

-.

Retrieved from "https://kanterella.com/w/index.php?title=TXX-4600,_Final_Deficiency_Rept_SDAR-193_Re_Potential_Loss_of_Control_Capability_of_Feedwater_Regulating_Valve.Initially_Reported_on_850827.Condition_Not_Reportable_Under_10CFR50.55(e)&oldid=4236481"